Author: G. R. BradyPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Post-irradiation examination of a cold-worked zirconium-2.5 percent nb pressure tube irradiated at 400 degrees c in the WR-1 reactor
Author: G. R. BradyProposal for the post-irradiation examination of the heat-treated zr-2.5 percent nb pressure tube from the x-5 loop
Author: W. J. LangfordPost-irradiation examination of a zr-2.5 nb pressure tube from the u-1 loop. (assembly #50205).
Author: M. Resta LeviEffect of Long-Term Irradiation on the Fracture Properties of Zr-2.5Nb Pressure Tubes
Author: S. SagatPublisher:
ISBN:
Category : Fracture
Languages : en
Pages : 17
Book Description
Results from fracture toughness and tensile and delayed hydride cracking (DHC) tests on Zr-2.5Nb pressure tubes removed from CANDU power reactors in the 1970s and 80s for surveillance showed considerable scatter. At that time, the cause of the scatter was unknown and prediction of fracture toughness to the end of the design life of a CANDU reactor using the surveillance data was difficult. To eliminate the heat-to-heat variability and to determine end-of-life mechanical properties, a program was undertaken to irradiate, in a high-flux reactor, fracture toughness, DHC, and transverse tensile specimens from a single "typical" pressure tube. Two inserts were placed in the OSIRIS reactor at CEA, Saclay, in 1988. Each insert held 16 of each type of specimen. The first insert, ERABLE 1, was designed so that half the specimens could be replaced at intervals and the properties could be measured as a function of fluence. All the specimens would be removed after a total fluence of 15 x 1025 n . m-2, E > 1 MeV. The second insert, ERABLE 2, was designed to run without interruption to a fluence of 30 x 1025 n . m-2, the fluence corresponding to 30 years' operation of a CANDU reactor at 90% capacity factor. The irradiation temperature was chosen to be 250°C, the inlet temperature of early CANDU reactors. The irradiation of ERABLE 1 has been completed and sets of specimens have been removed and tested with maximum fluences of approximately 0.7, 1.7, 2.8, 12, and 17 x 1025 n . m-2, E > 1 MeV. X-ray and TEM examinations have been performed on the material from fractured specimens to characterize the irradiation damage. Results showed that there is, initially, a large change in the mechanical properties before a fluence of 0.6 x 1025 n . m-2, E > 1 MeV (corresponding to an initial rapid increase in a-type dislocation density), followed by a gradual change. As expected, the fracture toughness decreased with fluence, whereas the yield strength, UTS, and DHC crack velocities all increased. Z-ray analysis showed that, although the a-type dislocation density remained constant after the initial increase, the number of c-component dislocations showed a steady increase, agreeing with the behavior seen in the mechanical specimens. Because the flux in OSIRIS is different from that in a CANDU reactor, specimens were also irradiated in NRU, a heavy water moderated test reactor with approximately the same flux as a CANDU reactor, to fluences of 0.3, 0.6, and 1.0 x 1025 n.m-2, E > 1 MeV for comparison. These initial results show that, once past the initial transient, one can have confidence that there will be little further degradation with fluence, with the results from the NRU specimens being similar to those from OSIRIS.
Basic Studies in the Field of High-temperature Engineering
Author: Nihon Genshiryoku KenkyūjoPublisher: Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development
ISBN:
Category : Science
Languages : en
Pages : 370
Book Description
In response to increasing interest in high-temperature, gas-cooled reactors (HTGRs) in many countries and the need for improved materials for nuclear applications in high-temperature environments, the NEA organised a Second Information Exchange Meeting on Basic Studies in the Field of High-temperature Engineering. These proceedings provide an overview of the activities being carried out in eight countries, the improvement of material properties for HTGR application, in-core monitoring methods and properties of irradiated graphite, and HTGR fuel fabrication and performance.
Electrostatic Levitator
Author: Publisher:
ISBN:
Category : Reduced gravity environments
Languages : en
Pages : 6
Book Description
The Use of Portable Power Tools
Author: Leo P. McDonnellPublisher:
ISBN:
Category : House & Home
Languages : en
Pages : 232
Book Description
Uranium Ore Processing
Author: Climate Change and the Role of Nuclear Power
Author: International Atomic Energy AgencyPublisher:
ISBN: 9789201201201
Category :
Languages : en
Pages : 215
Book Description
To address the challenges posed by climate change, and to achieve the goals established in the 2015 Paris Agreement, nuclear power has been identified to have great potential to contribute to the 1.5°C climate change mitigation target. This topical conference on climate change and the role of nuclear power, the first of its kind, served as a unique forum for exchanging science-based information on the role of nuclear power in supporting the low carbon energy transformation and for conducting objective discussions on the opportunities and challenges of safe, secure and safeguarded nuclear technology development. The major themes of the conference covered energy and climate change policies, implications for the power sector, environmental perspectives and potential roles of existing, evolutionary and innovative nuclear power systems, including the integration of nuclear/renewable energy systems. In addition to nuclear power's interim and long term contributions, some strategic and cross-cutting issues relating to public perception, regulations, markets and finance were also addressed. These proceedings provide a summary of the different plenary, technical and side event sessions as well as the full text of the speeches delivered in the opening, closing and high-level plenary sessions of the conference.